Segmented Transfer Cask with Removable Shielding Sleeve

Resolve Bottlenecks,
Find Innovative Solutions
Generate Solutions

Solution Overview

Problem

Existing transfer casks for spent nuclear fuel face challenges with size and weight limitations in wet storage facilities, leading to increased radiation exposure and safety risks during the transfer process from wet to dry storage, as they often require additional shielding that exceeds facility capacity.

Innovation Solution

A two-piece transfer cask system comprising a lightweight, partially shielded transfer cask with a smaller diameter and a removable shielding sleeve that provides supplemental radiation shielding during transfer, allowing simultaneous lifting and support by a lifting system to address both size and weight constraints.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Object-affected harmful factors

If a transfer cask is designed with adequate radiation shielding, then radiation exposure during transfer is reduced, but the size and weight of the cask increase, exceeding facility capacity limits

Engineering Contradiction:
Improveradiation exposureVSAvoidtransfer cask weight
Core Design Contradiction:
Object-affected harmful factorsVSWeight of moving object

Solution Approach 1:

The shielding function is segmented between the transfer cask structure and a separate removable shielding sleeve. The transfer cask provides basic shielding while the additional sleeve provides supplemental shielding when needed during transfer operations, allowing the base cask to remain within facility weight limits while achieving adequate total shielding when required.

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

A removable shielding sleeve acts as an intermediary component that can be added to or removed from the transfer cask. This sleeve provides the additional radiation shielding needed during transfer without permanently increasing the base cask weight, allowing the system to adapt shielding levels to operational requirements.

Inventive Principle:
Principle #24Intermediary (Mediator)

2Object-affected harmful factors

If a transfer cask is designed with adequate radiation shielding, then radiation exposure during transfer is reduced, but the diameter of the cask increases, exceeding facility size limits

Engineering Contradiction:
Improveradiation exposureVSAvoidtransfer cask diameter
Core Design Contradiction:
Object-affected harmful factorsVSLength of moving object

Solution Approach 1:

The shielding function is segmented between the transfer cask structure and a separate removable shielding sleeve. The transfer cask maintains a diameter within facility limits while the additional shielding sleeve provides supplemental radiation protection when needed during transfer operations.

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

A removable shielding sleeve acts as an intermediary component that can be added to or removed from the transfer cask. This sleeve provides the additional radiation shielding needed during transfer without permanently increasing the base cask diameter, allowing the system to adapt shielding levels to operational requirements.

Inventive Principle:
Principle #24Intermediary (Mediator)

3Weight of moving object

If a transfer cask is made lightweight to fit facility weight limits, then size constraints are satisfied, but radiation shielding capability is reduced, increasing radiation exposure

Engineering Contradiction:
Improvetransfer cask weightVSAvoidradiation exposure
Core Design Contradiction:
Weight of moving objectVSObject-affected harmful factors

Solution Approach 1:

The shielding function is segmented between the transfer cask structure and a separate removable shielding sleeve. The transfer cask provides basic shielding while the additional sleeve provides supplemental shielding when needed during transfer, allowing the base cask to remain within facility weight limits while achieving adequate total shielding when required.

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

The shielding configuration is made dynamic through the removable shielding sleeve that can be added or removed based on operational requirements. During transfer operations, the sleeve is attached to provide enhanced shielding, while the base cask maintains a lightweight design for facility compliance.

Inventive Principle:
Principle #15Dynamics

4Length of moving object

If a transfer cask is made small in diameter to fit facility size limits, then weight constraints are satisfied, but radiation shielding capability is reduced, increasing radiation exposure

Engineering Contradiction:
Improvetransfer cask diameterVSAvoidradiation exposure
Core Design Contradiction:
Length of moving objectVSObject-affected harmful factors

Solution Approach 1:

The shielding function is segmented between the transfer cask structure and a separate removable shielding sleeve. The transfer cask provides basic shielding while the additional sleeve provides supplemental shielding when needed during transfer, allowing the base cask to maintain a compact diameter within facility limits while achieving adequate total shielding when required.

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

A removable shielding sleeve acts as an intermediary component that can be added to or removed from the transfer cask. This sleeve provides the additional radiation shielding needed during transfer without permanently increasing the base cask diameter, allowing the system to adapt shielding levels to operational requirements.

Inventive Principle:
Principle #24Intermediary (Mediator)

Data Source

PatentUS11728058B2Systems and methods for transferring spent nuclear fuel from wet storage to dry storage
Publication Date: 2023.08.15 NAC INTERNATIONAL INC
  • US11728058B2 patent drawing
  • US11728058B2 patent drawing
  • US11728058B2 patent drawing

AI summary

Systems and methods of transferring nuclear fuel from fuel pools having size and/or weight limitations to a storage or transport cask are disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. A shielding sleeve is then placed around the transfer cask. A lifting device simultaneously lifts the transfer cask and the shielding sleeve over a storage cask and the spent fuel is transferred from the transfer cask to the storage or transport cask.