公开(公告)号：US11810684B2

公开(公告)日：2023-11-07

申请号：US17410097

申请日：2021-08-24

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Ki Rak Lee ,  Hwan Seo Park ,  Geun Il Park ,  Hong Joo Ahn ,  Jung Hoon Choi ,  Hyun Woo Kang ,  In Tae Kim

IPC: G21F9/30 ,  B01D53/00 ,  B01D53/04 ,  G21F9/08 ,  G21F9/12

CPC classification number: G21F9/30 ,  B01D53/002 ,  B01D53/04 ,  G21F9/08 ,  G21F9/12 ,  B01D2253/10 ,  B01D2257/708 ,  B01D2259/40088

Abstract: The present invention relates to a method of separating and removing a radioactive nuclide, particularly, C-14 and tritium from a radioactive waste resin, and an equipment therefor. The method of treating a radioactive waste resin of the present invention includes recycling of condensate water from which a C-14 radionuclide in the condensate water is removed, into a treatment part for a radioactive waste resin.

公开(公告)号：US20130289329A1

公开(公告)日：2013-10-31

申请号：US13654292

申请日：2012-10-17

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE

Inventor： Chang Hwa LEE ,  Min Ku JEON ,  Kweon Ho KANG ,  Geun Il Park

IPC: G21F9/30

CPC classification number: G21F9/30 ,  G21F9/308

Abstract: The present disclosure relates to a decontamination method and apparatus for cladding hull wastes of spent nuclear fuels, capable of decontaminating a small quantity of spent nuclear fuels remaining on surfaces of the cladding hull wastes and radioactive fission products penetrated into the cladding hulls through an electrochemical dissolution. The method includes inserting the cladding hull waste into an anodic basket, immersing a reference electrode and a cathodic electrode as well as the anodic basket in a molten salt, dissolving a surface of the cladding hull waste by applying a voltage or current to the anodic basket with respect to the cathodic electrode or the reference electrode, removing the anodic basket, and removing a salt remaining on the surface of the cladding hull waste.

Abstract translation: 本公开涉及一种用于包覆废核燃料的船体废物的净化方法和装置，其能够净化通过电化学溶解渗透到包壳中的少量废弃核燃料残留在包壳船体废物的表面和放射性裂变产物 。 该方法包括将包壳体废物插入阳极筐中，将参考电极和阴极电极以及阳极筐浸入熔融盐中，通过向阳极筐施加电压或电流来溶解包壳体废物的表面 相对于阴极电极或参考电极，去除阳极筐，并除去残留在包壳体废物表面上的盐。

公开(公告)号：US08535636B1

公开(公告)日：2013-09-17

申请号：US13624744

申请日：2012-09-21

Applicant: Korea Atomic Energy Research Institute ,  Korea Hydro & Nuclear Power Co., Ltd.

Inventor： Hee Chul Eun ,  Yung Zun Cho ,  Hwan Seo Park ,  Tae Kyo Lee ,  In Tae Kim ,  Geun Il Park

IPC: C01F5/00

CPC classification number: G21C19/48 ,  C01D15/04 ,  C01F11/02 ,  C01F11/24 ,  G21F9/28 ,  G21F9/32 ,  Y02W30/884

Abstract: Disclosed herein is a method of separating group II nuclides from a radioactive waste lithium chloride salt and recovering renewable lithium chloride, comprising the steps of: injecting lithium oxide into a lithium chloride salt containing group II nuclides to convert the group II nuclides into thermally-stable oxide or oxychloride; and vaporizing and condensing the lithium chloride salt under a reduced pressure condition to separate the group II nuclides and recover recyclable lithium chloride. The method is advantageous in that group II nuclides existing in the form of chloride, which is not highly thermally-stable in a lithium chloride (LiCl) to salt and is not easily solidified, can be converted into oxides or oxychlorides, which is highly thermally-stable in the lithium chloride (LiCl) salt and is easily solidified, without producing impurities.

Abstract translation: 本文公开了一种从放射性废物氯化锂盐中分离II族核素并回收可再生氯化锂的方法，包括以下步骤：将锂氧化物注入含II族核素的氯化锂盐中，将II族核素转化为热稳定性 氧化物或氯氧化物; 并在减压条件下蒸发和冷凝氯化锂盐，以分离第二组核素，并回收可再循环的氯化锂。 该方法的优点在于以氯化锂（LiCl）对盐不高度热稳定并且不容易固化的以氯化物形式存在的II族核素可以转化为高度热的氧化物或氯氧化物 - 稳定在氯化锂（LiCl）盐中，并且容易固化，而不产生杂质。