# US 2014/0151215 A1 · Separation and Recovery Device for Liquid Waste Including Radionuclide, and Separation and Recovery Method Using the Same > Agents: this data is available as JSON from the patentgrep API and MCP server — see https://patentgrep.com/llms.txt - Number: US 2014/0151215 A1 - Document ID: US20140151215A1 - Status: Published application - Kind: A1 - Application number: 14/077,001 - Filed: 2013-11-11 - Published: 2014-06-05 - Earliest claimed: 2012-11-30 - Assignees: Korea Atomic Energy Research Institute - Applicants: Korea Atomic Energy Research Institute - Inventors: Hee-Chul Yang; Dong Yong Chung; Jeikwon Moon - Web page: https://patentgrep.com/patent/US20140151215A1 ## CPC - B01D 5/009: {Collecting, removing and/or treatment of the condensate} - B01D 5/006: {with evaporation or distillation} - B01D: SEPARATION (separating solids from solids by wet methods B03B, B03D; by pneumatic jigs or tables B03B; by other dry methods B07; magnetic or electrostatic separation of solid materials from solid materials or fluids, separation by high-voltage electric fields B03C; centrifuges, vortex apparatus B04; presses per se for squeezing-out liquid from liquid-containing material B30B9/02; treatment of water C02F, e.g. softening by ion-exchange C02F1/42; {arrangements of air intake cleaners in gas turbine plants F02C7/05} ; arrangements or mounting of filters in air-conditioning, air-humidification or ventilation F24F13/28) ## Abstract Provided are a separation and recovery device for a liquid waste including a radionuclide, and a separation and recovery method using the same. Specifically, the present disclosure relates to a separation and recovery device that may effectively separate a liquid waste, such as a waste detergent including a radionuclide, and simultaneously, may prevent the release of tritium and radiocarbon to the outside, and a separation and recovery method using the same. ## Claims ### Claim 1 A separation and recovery device for a liquid waste including a radionuclide, the separation and recovery device comprising: a liquid waste storage unit that stores a liquid waste mixture including a radionuclide; a heating unit that heats the liquid waste storage unit to evaporate a low boiling point liquid waste including a radionuclide from the liquid waste mixture in the liquid waste storage unit; a condensation chamber that is connected to an upper portion of the heating unit and condensates the liquid waste evaporated by heating by the heating unit; a condensate recovery unit that is connected to the condensation chamber and recovers a condensate condensed in the condensation chamber; and a transfer tube that transfers the condensate condensed in the condensation chamber to the condensate recovery unit, in which one end of the transfer tube is dipped in the condensate in the condensate recovery unit, wherein the evaporated low boiling point liquid waste moves from the heating unit to the condensate recovery unit by a pressure difference between the heating unit and the condensate recovery unit, and the radionuclide evaporated by the heating unit is recovered by being dissolved in the condensate that is recovered in the condensate recovery unit. ### Claim 2 (depends on 1) The separation and recovery device for a liquid waste including a radionuclide as set forth in claim 1, wherein the liquid waste mixture is a waste detergent including waste oil or wastewater including a fluorescent liquid waste. ### Claim 3 (depends on 1) The separation and recovery device for a liquid waste including a radionuclide as set forth in claim 1, wherein the radionuclide is tritium (H-3) or radiocarbon (C-14). ### Claim 4 (depends on 1) The separation and recovery device for a liquid waste including a radionuclide as set forth in claim 1, further comprising a vacuum pump that is linked with the condensate recovery unit. ### Claim 5 (depends on 1) The separation and recovery device for a liquid waste including a radionuclide as set forth in claim 1, further comprising a transfer device that transfers the liquid waste storage unit to the heating unit, wherein the liquid waste storage unit and the heating unit are allowed to be spaced apart from each other. ### Claim 6 (depends on 1) The separation and recovery device for a liquid waste including a radionuclide as set forth in claim 1, wherein the heating unit is included in a form of surrounding the liquid waste storage unit and indirectly heats the liquid waste storage unit by using heat medium oil. ### Claim 7 (depends on 1) The separation and recovery device for a liquid waste including a radionuclide as set forth in claim 1, further comprising thermocouples that respectively measure temperatures of the heating unit and the liquid waste storage unit. ### Claim 8 (depends on 1) The separation and recovery device for a liquid waste including a radionuclide as set forth in claim 1, further comprising a chiller that cools the condensate recovery unit. ### Claim 9 (depends on 1) The separation and recovery device for a liquid waste including a radionuclide as set forth in claim 1, wherein the condensation chamber is a transparent container, in which an inside thereof is visible from outside. ### Claim 10 (depends on 1) The separation and recovery device for a liquid waste including a radionuclide as set forth in claim 1, wherein the condensation chamber has an inclined form so that the condensate is transferred to the condensate recovery unit when more than a predetermined amount of the evaporated liquid waste is condensed. ### Claim 11 (depends on 1) A method of separating and recovering a liquid waste including a radionuclide by using the separation and recovery device of claim 1, the method comprising: heating a liquid waste mixture including a radionuclide to evaporate a low boiling point liquid waste including the radionuclide (step 1); condensing the low boiling point liquid waste evaporated in step 1 and then recovering a condensate to a condensate recovery unit (step 2); and dipping one end of a transfer tube in the condensate recovered in step 2 to dissolve the evaporated radionuclide in the condensate in the condensate recovery unit (step 3). ### Claim 12 (depends on 11) The method as set forth in claim 11, wherein the heating of step 1 is performed at a temperature at which a high boiling point liquid waste is not evaporated but only the low boiling point liquid waste is evaporated. ### Claim 13 (depends on 11) The method as set forth in claim 11, wherein the radionuclide of step 1 is tritium (H-3) or radiocarbon (C-14).