Bioprotective Concrete Decontamination via Lower Penetration Access

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Solution Overview

Problem

The dismantling and decontamination of bioprotective concrete in nuclear power plants pose risks of radiation exposure and dust spread due to its high radioactivity, necessitating a safer and more efficient process.

Innovation Solution

A system comprising a dismantling device to create a lower penetrated part, a decontamination device for inner wall cleaning, a waste receiving device for waste management, and a dust blocking device to contain radioactive dust, along with a dust collecting device to minimize exposure.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Ease of manufacture

If a separate through-hole is formed for inserting the decontamination device into the bioprotective concrete, then the decontamination process can be performed, but there is a concern of radioactive exposure and movement of radioactive dust

Engineering Contradiction:

Improvedecontamination process accessibilityVSAvoidradioactive exposure and dust movement

Core Design Contradiction:

Ease of manufactureVSObject-affected harmful factors

Solution Approach 1:

The decontamination device is inserted through the lower penetrated part formed by dismantling the in-core instrument, utilizing the existing space rather than creating a separate through-hole. The waste receiving device is nested within the bioprotective concrete structure, with waste being moved through the lower penetrated part to avoid opening the upper opening.

Inventive Principle:

Principle #7Nested doll (Nesting)

Solution Approach 2:

The lower penetrated part serves as an intermediary channel for both inserting the decontamination device and removing waste. The dust blocking device acts as an intermediary barrier at the upper opening to prevent dust escape while allowing the process to proceed.

Inventive Principle:

Principle #24Intermediary (Mediator)

2Productivity

If the upper opening of the bioprotective concrete is opened for waste removal, then waste can be taken out, but radioactive dust may escape and workers may be exposed

Engineering Contradiction:

Improvewaste removal efficiencyVSAvoidradioactive dust escape and worker exposure

Core Design Contradiction:

ProductivityVSObject-affected harmful factors

Solution Approach 1:

The waste receiving device is positioned within the bioprotective concrete structure, and waste is moved through the lower penetrated part rather than requiring opening the upper opening. This nested arrangement allows waste removal while maintaining the seal of the upper opening.

Inventive Principle:

Principle #7Nested doll (Nesting)

Solution Approach 2:

Instead of removing waste vertically through the upper opening, the system utilizes the lower penetrated part as an alternative dimension for waste removal. This changes the waste ejection direction from upward to downward, preventing dust escape.

Inventive Principle:

Principle #17Another dimension (Dimensionality change)

3Reliability

If the decontamination process is performed thoroughly, then radioactive waste is removed, but the process time increases and worker exposure time increases

Engineering Contradiction:

Improvedecontamination effectivenessVSAvoiddecontamination process time and worker exposure time

Core Design Contradiction:

ReliabilityVSLoss of time

Solution Approach 1:

The waste receiving device is nested within the bioprotective concrete and can be moved through the lower penetrated part repeatedly. This allows frequent waste removal without opening the upper opening, reducing both process time and worker exposure time while maintaining thorough decontamination.

Inventive Principle:

Principle #7Nested doll (Nesting)

Solution Approach 2:

The system enables continuous decontamination operations by allowing the waste receiving device to be moved in and out through the lower penetrated part multiple times. This continuous operation eliminates the need to stop and open the upper opening for waste removal, maintaining productive action throughout the process.

Inventive Principle:

Principle #20Continuity of useful action

Data Source

PatentUS20250364149A1Dismantling and decontamination system and method of bioprotective concrete of PWR type nuclear power plant

Publication Date: 2025.11.27 KOREA HYDRO & NUCLEAR POWER CO LTD

AI summary

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