Korea Atomic Energy Research Institute

Korea Hydro Nuclear Power Co., Ltd.

Hwan Seo Park

Yung-Zun Cho

Jung Hoon Choi

Geun Il Park

Hong Joo Ahn

Ki Rak Lee

In Tae Kim

Jong Kwang Lee

Geun-Il Park

In-Tae Kim

Hee-Chul Yang

Hansoo Lee

Kwang Jae Son

Byung-Gil Ahn

Hee Chul Eun

Hwan-Young Kim

Hee-Chul Eun

Yung Zun Cho

Tae-Kyo Lee

Tae Kyo Lee

JunHong Kim

Hyun Woo Kang

The present invention relates to a method for simultaneous analysis of radiocarbon and tritium, the method including (i) mixing a radioactive waste sample containing a radiocarbon nuclide and tritiated water, and an oxidizing agent; (ii) oxidizing the radiocarbon nuclide in the radioactive waste sample to a gas containing an oxide of the radiocarbon nuclide by the oxidizing agent while suppressing volatilization of compounds containing gamma radionuclides other than the radiocarbon nuclide and tritium; (iii) discharging the gas containing an oxide of the radiocarbon nuclide by injecting an inert gas to the mixture; (iv) vaporizing and discharging the tritiated water in the mixture; and (v) analyzing radioactivity of radiocarbon and tritium from the discharged gas containing an oxide of the radiocarbon nuclide and tritiated water, and an apparatus for analysis of the same.

Method for simultaneous analysis of radiocarbon and tritium

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.

Method of treating radioactive waste resin and an equipment therefor

There are provided an apparatus and method for separating radioactive nuclides from a waste salt and recovering a refined salt, which are able to maximize process efficiency and operating efficiency of a process of regenerating a waste salt produced during a pyrochemical process of used nuclear fuel by converting the waste salt into a thermally stable form and distilling the waste salt under a reduced pressure using a single apparatus having two top covers which are mountable to replace radioactive nuclides included in the waste salt, and highly improve applicability and utility in a remote operation facility for disposal of a radioactive waste by further simplifying operation/handling compared with conventional processes.

Apparatus and method for separating radioactive nuclides and recovering refined salt from LiCl waste salt or LiCl-KCI eutectic waste salt

The present invention relates to a method and apparatus for solidifying radioactive waste accompanying chlorine recycling or radioactive iodine removal. The present invention provide a method and apparatus for treating radioactive waste composed of volatile metal halide with high corrosiveness at a high temperature through a solidifying system including crushing, mixing/dehalogenating and sintering. In the inventive method and apparatus for solidifying radioactive waste, a dechlorination process by using a dehalogenation material is performed on highly corrosive metal salt under an oxidizing atmosphere by using a method of controlling a temperature on the surface of a reactor, and solidification is carried out by removing radioactive iodine while reusing chlorine contained in an exhaust gas. Accordingly, the generated amount of total waste can be reduced, and therefore the inventive method and apparatus can be usefully used in preparing a solidified body with high durability.

Solidification method of radioactive waste accompanying chloride recycling or radioactive iodide removing and the device thereof

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.

Method of separating group II nuclides from radioactive waste lithium chloride salt and recovering pure lithium chloride using lithium oxide

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Daejeon, South Korea

Hwan Seo Park