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公开(公告)号：JP2016186496A
公开(公告)日：2016-10-27
申请号：JP2016120397
申请日：2016-06-17
Applicant: アドバンスト・リアクター・コンセプツ・エルエルシー
Inventor： ウォルターズ,レオン・シー
IPC: G21C3/64
CPC classification number: G21C15/00 , G21C19/44 , G21C21/04 , G21C3/02 , G21C3/60 , G21C1/07 , G21C3/07 , Y02E30/34 , Y02E30/38 , Y02W30/882
Abstract: 【課題】軽水炉の使用済み燃料中になお含有されているエネルギーをアクチニドの存在を通して回収する。 【解決手段】微粒子状金属燃料が、少なくとも1つの濃縮合金の粒子と、湿式再処理されていない破砕された軽水炉(LWR)使用済核燃料の粒子とを備えており、前記微粒子状金属燃料が、連続金属マトリックスを形成するために原子炉内で放射線を照射されたときに自己形成するサーメット燃料である、燃料カラムと、クラッディングと、ガス充填プレナムと、を備えている、金属燃料システム。 【選択図】図1
Abstract translation: 要解决的问题：通过存在锕系元素来回收轻水反应堆用过的燃料中的能量。解决方案：在金属燃料系统中，颗粒状金属燃料包括至少一种浓缩合金颗粒和使用的核燃料的粉碎颗粒 不进行水处理的轻水反应器（LWR），当在用于形成连续金属基质的原子反应器中进行辐射时，自发形成金属陶瓷燃料的颗粒状金属燃料，即燃料柱，包层和气体 - 填充的会议室。图1
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公开(公告)号：JP5593525B2
公开(公告)日：2014-09-24
申请号：JP2010131058
申请日：2010-06-08
Applicant: 日立Geニュークリア・エナジー株式会社
IPC: G21C19/44
CPC classification number: Y02W30/882
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公开(公告)号：JP5574399B2
公开(公告)日：2014-08-20
申请号：JP2008323771
申请日：2008-12-19
Applicant: ウエスチングハウス・エレクトリック・カンパニー・エルエルシー
Inventor： エフ クーニー バリー , エム カムデン，ジュニア トーマス
CPC classification number: G21F9/34 , G21C19/44 , G21F9/36 , Y02W30/882
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公开(公告)号：JP5497426B2
公开(公告)日：2014-05-21
申请号：JP2009298093
申请日：2009-12-28
Applicant: 日立Geニュークリア・エナジー株式会社
CPC classification number: G21C3/328 , G21C1/084 , G21C3/42 , G21C5/00 , G21C5/02 , G21C19/44 , Y02E30/38 , Y02W30/882
Abstract: A core of a light water reactor has a plurality of fuel assemblies. The fuel assemblies include a plurality of fuel rods in which a lower end is supported by a lower tie-plate and an upper end is supported by an upper tie-plate. The fuel rods form plenums above a nuclear fuel material zone and have a neutron absorbing material filling zone under the nuclear fuel material zone. Neutron absorbing members attached to the upper tie-plate are disposed between mutual plenums of the neighboring fuel rods above the nuclear fuel material zone. The neutron absorbing members have a length of 500 mm and are positioned at a distance of 300 mm from the nuclear fuel material zone. Even if the overall core is assumed to become a state of 100% void, no positive reactivity is inserted to the core.
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公开(公告)号：JP2014034693A
公开(公告)日：2014-02-24
申请号：JP2012175575
申请日：2012-08-08
Applicant: Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
Inventor： FUJII KAZUMI , KANEDA JUNYA , TOYODA TETSUYA , NAGASE HIROSHI , YANOKURA YUKIO
Abstract: PROBLEM TO BE SOLVED: To provide a device for a nuclear fuel reprocessing plant in which corrosion resistance of locations in contact with nitric acid is improved.SOLUTION: A device for a nuclear fuel reprocessing plant is characterized in that locations in contact with nitric acid are coated with a metal or metal-oxide coating material having corrosion resistance to nitric acid. The metal is preferably at least one kind selected from Zr, Nb, Ta, Hf, Ti, Rh, and Pt.
Abstract translation: 要解决的问题：提供一种核燃料后处理装置的装置，其中与硝酸接触的位置的耐腐蚀性得到改善。解决方案：用于核燃料后处理装置的装置的特征在于与硝酸接触的位置是 涂覆有对硝酸具有耐腐蚀性的金属或金属氧化物涂层材料。 金属优选为选自Zr，Nb，Ta，Hf，Ti，Rh和Pt中的至少一种。
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Patent Agency Ranking
公开(公告)号：JP4450412B2
公开(公告)日：2010-04-14
申请号：JP2004025732
申请日：2004-02-02
Applicant: 財団法人電力中央研究所
CPC classification number: Y02W30/882
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公开(公告)号：JP2009294145A
公开(公告)日：2009-12-17
申请号：JP2008149575
申请日：2008-06-06
Applicant: Hitachi-Ge Nuclear Energy Ltd , 日立Geニュークリア・エナジー株式会社
Inventor： ABE TAKASHI , SASAHIRA AKIRA , HOSHINO KUNIYOSHI , FUKAZAWA TETSUO , KAWAMURA FUMIO
IPC: G21C19/44
CPC classification number: Y02W30/882
Abstract: PROBLEM TO BE SOLVED: To provide a recycling method of uranium from spent nuclear fuel improving the recovery rate of plutonium, even if a uranium separation method with a high amount of accompanying Pu is used. SOLUTION: The recycling method of uranium from spent nuclear fuel in which UF 6 is obtained from spent nuclear fuel includes a uranium separation step to separate recovered uranium 5 from spent nuclear fuel 11; a fluorination device 1 for fluorination-volatilizing the recovered uranium 5 obtained in the uranium separation step; and a uranium-based absorbent trap 4 for capturing plutonium as solid uranium compounds from the recovered uranium 5 fluorinated and volatilized by the fluorination device, and the plutonium captured by the uranium absorbent trap 4 is returned to the previous or next step of the uranium separation step. COPYRIGHT: (C)2010,JPO&INPIT
Abstract translation: 要解决的问题：即使使用具有大量附带的铀的铀分离方法，提供废核燃料中的铀的再循环方法提高了钚的回收率。 解决方案：从废核燃料中获得UF
6 的乏核燃料的铀回收方法包括将回收的铀5与乏核燃料11分离的铀分离步骤; 用于氟化挥发在铀分离步骤中获得的回收铀5的氟化装置1; 以及铀基吸收剂捕集器4，用于从被氟化装置氟化并挥发的回收的铀5捕获钚作为固体铀化合物，并且由铀吸收剂捕集器4捕获的钚返回到铀分离的先前或下一步骤 步。 版权所有（C）2010，JPO＆INPIT -
公开(公告)号：JP4247410B2
公开(公告)日：2009-04-02
申请号：JP2004209621
申请日：2004-07-16
Applicant: 独立行政法人 日本原子力研究開発機構
Inventor： 哲雄 池上
CPC classification number: Y02E30/34 , Y02E30/38 , Y02W30/881 , Y02W30/882
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9.发明专利Molten salt electrolytic refiner and molten salt electrolytic refining method 有权MOLTEN盐电解精炼机和MOLTEN盐电解精炼方法
公开(公告)号：JP2008266662A
公开(公告)日：2008-11-06
申请号：JP2007106891
申请日：2007-04-16
Applicant: Toshiba Corp , 株式会社東芝
Inventor： NAKAMURA HITOSHI , FUJITA REIKO , FUSE YUKIMOTO , KAWABE AKIHIRO , UTSUNOMIYA KAZUHIRO
CPC classification number: Y02W30/882
Abstract: PROBLEM TO BE SOLVED: To efficiently recover a large amount of U and TRU without increasing an amount of liquid metal used as an anode by steadily maintaining the interface of a liquid metal electrode of a molten salt electrolytic refiner to an original composition. SOLUTION: The molten salt electrolytic refiner having an electrolytic cell installed in an electric furnace and housed with a molten salt, an anode container charged with a used nuclear fuel, and a liquid metal crucible housed with liquid metal cathode is equipped with a compressive apparatus which compresses the solid precipitated object generated at the interface of the liquid metal cathode to a liquid metal cathode bottom. COPYRIGHT: (C)2009,JPO&INPIT
Abstract translation: 要解决的问题：通过将熔融盐电解精炼机的液态金属电极的界面稳定地维持在原始组成上，能够有效地回收大量的U和TRU，而不会增加用作阳极的液态金属的量。 解决方案：将具有安装在电炉中并装有熔融盐的电解池，装有使用的核燃料的阳极容器和容纳有液态金属阴极的液态金属坩埚的熔融盐电解精炼机配备有 压缩装置，其将在液态金属阴极的界面处产生的固体沉淀物压缩到液态金属阴极底部。 版权所有（C）2009，JPO＆INPIT
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10.发明专利Reductor and lithium reclamation electrolysis device of spent oxide nuclear fuel 有权氧化氮核燃料的还原剂和锂回收电解装置
公开(公告)号：JP2008134096A
公开(公告)日：2008-06-12
申请号：JP2006318990
申请日：2006-11-27
Applicant: Toshiba Corp , 株式会社東芝
Inventor： KAWABE AKIHIRO , FUJITA REIKO , MIZUGUCHI KOJI , FUSE YUKIMOTO , NAKAMURA HITOSHI , OKANIWA MASAAKI
IPC: G21C19/44
CPC classification number: Y02W30/882
Abstract: PROBLEM TO BE SOLVED: To provide a reductor for reclaiming spent oxide nuclear fuel which includes electrodes that are free from problems with corrosion resistance even in the use in high-temperature molten salt as electrodes used in the reclamation of spent oxide nuclear fuel and also problems with an electrical short circuit caused by the missing of any electrode materials and the like. SOLUTION: In the reductor 10 where the spent oxide nuclear fuel 16 held by the cathode 11 and the anode 12 are submerged in a molten salt 13, current 15 is passed through the cathode 11 and the anode 12 and reduction treatment is given to oxides of uranium, plutonium and minor actinides contained in the spent oxide fuel 16 to obtain uranium, plutonium and minor actinides from the spent oxide nuclear fuel 16 by reclaiming them in the form of metal; an oxide ion conductive solid electrolyte is used as the anode 12. COPYRIGHT: (C)2008,JPO&INPIT
Abstract translation: 要解决的问题：提供一种用于回收废氧化物核燃料的还原剂，其包括即使在高温熔盐中用作废氧化物核燃料的回收中使用的电极也不具有耐腐蚀性的问题 以及由于任何电极材料等的缺失引起的电气短路的问题。 解决方案：在由阴极11和阳极12保持的废氧化物核燃料16浸没在熔融盐13中的电极10中，电流15通过阴极11和阳极12，并给出还原处理 包含在废氧化物燃料16中的铀，钚和次锕系元素的氧化物，以通过以金属形式回收来从废氧化物核燃料16获得铀，钚和次锕系元素; 使用氧化物离子传导性固体电解质作为阳极12.版权所有（C）2008，JPO＆INPIT
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