
[기계신문] Since the inner surface of the reactor is exposed to cooling water, it is covered with a corrosion-resistant stainless steel cladding (protective layer) to prevent corrosion. In some cases, cases of cladding damage have been reported. If an operator performs welding repairs in water, it may be exposed to radiation above the standard value and the material surface may become brittle.
However, the Korea Atomic Energy Research Institute recently developed a standard procedure and related equipment for the’cladding damage repair technology using nickel (Ni) plating method’. Damaged parts of nuclear power plants can be repaired only by standard procedures that have undergone numerous verification tests. This time, the’Standard Procedure for Plating Repair of Damaged Parts of Nuclear Power Plants’ was developed so that the technology can be applied to the field.
Initially, this technology was developed by the researcher in 2013 through the nuclear R&D project of the Ministry of Science and ICT and received ASME certification, an international technology standard. ASME is an abbreviation of the American Society of Mechanical Engineers and its standards, and is a technical standard for the design, manufacture, and inspection of boilers and pressure vessels that are used worldwide. Since then, we have devoted ourselves to the development of maintenance standard procedures and equipment so that the technical standards can be implemented.

If you use the’Cladding damage repair technology using Ni plating method’, you can make a metal protective film remotely and repair it. It is a specially manufactured device that supplies a plating solution containing Ni components to the damaged area and passes current to create a protective film. Unlike the welding method in which the worker directly applies heat in water, it is evaluated as a breakthrough technology that fundamentally blocks material degeneration or the worker’s exposure to radiation.
The researcher plans to collaborate with the US Electric Power Research Institute (EPRI) so that the technology can be approved for a technical review by the US Regulatory Authority (USNRC). Several power plants in the United States and Europe have already recognized the excellence of technology and have expressed their intention to apply it to the repair of damaged parts of reactor vessels. After passing the technical review approval, it is expected to establish itself as an international nuclear standard technology for repairing nuclear reactor vessel damage.
“It is of great significance in that domestic nuclear source technology can be directly applied to the site to improve the safety of nuclear power plants,” said Sungsik Hwang, a researcher at the Department of Material Safety Technology Development who led the technology development. We will promote technology export.”
Machinery News, Machinery Industry News Channel
Reporter Oh Sang-mi [email protected]