Dismantling and decontamination system and method of bioprotective concrete of PWR type nuclear power plant

Patent metadata

Field	Value
Publication number	US-12437892-B2
Application number	US-201917048222-A
Country	US
Kind code	B2
Filing date	Apr 17, 2019
Priority date	Apr 17, 2018
Publication date	Oct 7, 2025
Grant date	Oct 7, 2025

Abstract

A dismantling and decontamination system of biodegradable concrete of a nuclear power plant according to an exemplary embodiment includes: a dismantling device for dismantling an in-core instrument installed under biodegradable concrete to form a lower penetrated part of the biodegradable concrete; a decontamination device inserted inside the biodegradable concrete for decontaminating radioactive waste of the inner wall of the biodegradable concrete; a waste receiving device movable through the lower penetrated part of the biodegradable concrete; and a blocking device for blocking the upper opening of the biodegradable concrete to block an outflow of the radioactive dust.

First claim

The invention claimed is:

1. A dismantling and decontamination system for dismantling and decontaminating bioprotective concrete of a nuclear power plant, comprising:
a dismantling device configured to dismantle an in-core instrument to form a penetrated part of the bioprotective concrete, wherein the in-core instrument is installed within the bioprotective concrete at a lower part of the bioprotective concrete, and wherein the penetrated part is formed in the lower part of the bioprotective concrete;
a decontamination device configured to be inserted inside of an interior space of the bioprotective concrete for decontaminating radioactive waste of an inner wall of the bioprotective concrete forming the interior space, wherein the decontamination device, in its entirety, is inserted inside of the interior space of the bioprotective concrete;
a waste receiving device configured to move into the interior space of the bioprotective concrete through the penetrated part of the bioprotective concrete; and
a blocking device configured to contact an upper surface of the bioprotective concrete and block an upper opening of the interior space of the bioprotective concrete to block an outflow of radioactive dust.

2. The dismantling and decontamination system of the bioprotective concrete of the nuclear power plant of claim 1 , wherein
the waste receiving device includes:
a receiving unit receiving the radioactive waste; and
a moving unit for moving the receiving unit.

3. The dismantling and decontamination system of the bioprotective concrete of the nuclear power plant of claim 2 , wherein
the area of the receiving unit is adjustable from a first area able to pass through the penetrated part to a second area greater than the first area and smaller than a cross-sectional area of the interior space of the bioprotective concrete.

4. The dismantling and decontamination system of the bioprotective concrete of the nuclear power plant of claim 1 , wherein
the decontamination device includes a hammer or a scabbler.

5. The dismantling and decontamination system of the bioprotective concrete of the nuclear power plant of claim 1 , wherein
the dust blocking device includes a tent or a shield.

Assignees

• Korea Hydro & Nuclear Power Co

Inventors

• Hwang Seok-Ju
• Lee Mi-Hyun
• Hong Sung-Hoon
• Kim Cheon-Woo

Classifications

• G21F9/30

  Processing (separating different isotopes of the same chemical element B01D59/00) · CPC title

• G21F9/001

  Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof · CPC title

• G21F9/00

  Treating radioactively contaminated material; Decontamination arrangements therefor · CPC title

• G21F9/304

  Cement or cement-like matrix (compositional aspects C04B) · CPC title

• Y02E30/00

  Energy generation of nuclear origin · CPC title