▎ 摘　　要

NOVELTY - Peelable film solution comprises 3.5-14.93 wt.% polyvinyl alcohol, 1-5 wt.% polyethylene glycol, 0.005-0.3 wt.% graphene oxide, 15-30 wt.% 0.5-3 mol/l acid agent, 0-2 wt.% complexing agent and remainder of deionized water. USE - The peelable film solution is useful for radionuclide decontamination such as uranium, plutonium, strontium, cesium, and cobalt. ADVANTAGE - The prepared film has high mechanical properties than conventional decontamination polyvinyl alcohol films, and has tensile strength on the horizontal surface is 23.6-62.1 MPa, and tensile strength on the inclined and vertical surface is 19.1-52.3 MPa, high decontamination coefficient, and the decontamination efficiency of common radionuclides not less than 85%, improves the efficiency of nuclear use and reduces the need for secondary waste treatment. DETAILED DESCRIPTION - INDEPENDENT CLAIMS are included for the following: (1) a method for preparing the solution, involving (a) weighing graphene oxide powder and deionized water in a mass ratio of 1:100, dispersing the graphene oxide in deionized water, and ultrasonically peeling until a stable dark brown suspension is formed, and (b) preparing polyvinyl alcohol solution with a concentration of 5-15 wt.% in a water bath at 90 degrees C, measuring 1 pt. wt. polyvinyl alcohol solution, and mixing 0.005-0.43 pt. wt. dark brown stable graphene oxide suspension, adding polyethylene glycol, complexing agent and acid agent, and mixing well at room temperature; (2) a method of using the above-mentioned solution, involving performing spray molding, casting molding and/or manual coating molding, when used on the horizontal surface of buildings, equipment, and workpieces; and (3) a recovery and reprocessing process of a peelable film, involving (i) allowing the peelable solution to dry naturally for 8-72 hours, after construction, and peeling off the decontaminated surface by mechanical or manual peeling, and (ii) crushing the stripped peelable film in a closed glove box, mixing with water to form a recovered material liquid, heating, conveying to a supercritical water oxidation treatment device for treatment, discharging the waste gas produced after treatment through a gas filter, and performing exchange process by ion adsorption on the liquid containing radionuclides to complete the collection of radionuclides.